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Title: Thermal-hydraulic simulation of natural convection decay heat removal in the High Flux Isotope Reactor using RELAP5 and TEMPEST: Part 1, Models and simulation results

Abstract

A study was conducted to examine decay heat removal requirements in the High Flux Isotope Reactor (HFIR) following shutdown from 85 MW. The objective of the study was to determine when forced flow through the core could be terminated without causing the fuel to melt. This question is particularly relevant when a station blackout caused by an external event is considered. Analysis of natural circulation in the core, vessel upper plenum, and reactor pool indicates that 12 h of forced flow will permit a safe shutdown with some margin. However, uncertainties in the analysis preclude conclusive proof that 12 h is sufficient. As a result of the study, two seismically qualified diesel generators were installed in HFIR. 9 refs., 4 figs.

Authors:
; ; ; ;
Publication Date:
Research Org.:
Oak Ridge National Lab., TN (USA)
OSTI Identifier:
6511289
Report Number(s):
CONF-890173-2
ON: DE89006635
DOE Contract Number:  
AC05-84OR21400
Resource Type:
Conference
Resource Relation:
Conference: RELAPS users seminar, College Station, TX, USA, 31 Jan 1989; Other Information: Portions of this document are illegible in microfiche products
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 22 GENERAL STUDIES OF NUCLEAR REACTORS; HFIR REACTOR; AFTER-HEAT REMOVAL; COMPUTERIZED SIMULATION; FLUID FLOW; HEAT TRANSFER; HYDRAULICS; MELTDOWN; R CODES; REACTOR ACCIDENTS; REACTOR SAFETY; T CODES; ACCIDENTS; COMPUTER CODES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID MECHANICS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; MECHANICS; REACTORS; REMOVAL; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SAFETY; SIMULATION; TANK TYPE REACTORS; TEST REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; 220700* - Nuclear Reactor Technology- Plutonium & Isotope Production Reactors; 220600 - Nuclear Reactor Technology- Research, Test & Experimental Reactors; 220900 - Nuclear Reactor Technology- Reactor Safety

Citation Formats

Morris, D G, Wendel, M W, Chen, N C.J., Ruggles, A E, and Cook, D H. Thermal-hydraulic simulation of natural convection decay heat removal in the High Flux Isotope Reactor using RELAP5 and TEMPEST: Part 1, Models and simulation results. United States: N. p., 1989. Web.
Morris, D G, Wendel, M W, Chen, N C.J., Ruggles, A E, & Cook, D H. Thermal-hydraulic simulation of natural convection decay heat removal in the High Flux Isotope Reactor using RELAP5 and TEMPEST: Part 1, Models and simulation results. United States.
Morris, D G, Wendel, M W, Chen, N C.J., Ruggles, A E, and Cook, D H. 1989. "Thermal-hydraulic simulation of natural convection decay heat removal in the High Flux Isotope Reactor using RELAP5 and TEMPEST: Part 1, Models and simulation results". United States.
@article{osti_6511289,
title = {Thermal-hydraulic simulation of natural convection decay heat removal in the High Flux Isotope Reactor using RELAP5 and TEMPEST: Part 1, Models and simulation results},
author = {Morris, D G and Wendel, M W and Chen, N C.J. and Ruggles, A E and Cook, D H},
abstractNote = {A study was conducted to examine decay heat removal requirements in the High Flux Isotope Reactor (HFIR) following shutdown from 85 MW. The objective of the study was to determine when forced flow through the core could be terminated without causing the fuel to melt. This question is particularly relevant when a station blackout caused by an external event is considered. Analysis of natural circulation in the core, vessel upper plenum, and reactor pool indicates that 12 h of forced flow will permit a safe shutdown with some margin. However, uncertainties in the analysis preclude conclusive proof that 12 h is sufficient. As a result of the study, two seismically qualified diesel generators were installed in HFIR. 9 refs., 4 figs.},
doi = {},
url = {https://www.osti.gov/biblio/6511289}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Sun Jan 01 00:00:00 EST 1989},
month = {Sun Jan 01 00:00:00 EST 1989}
}

Conference:
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